ML17055E654

Requests Prompt Review & Reporting of Status of Implementation of TMI Action Plan Items at Facilities. Printout of All TMI Items,Annotated Where Tracking Sys Indicates Implementation Incomplete,Encl

ML17055E654
Person / Time
Site:	Nine Mile Point
Issue date:	04/14/1989
From:	Murley T Office of Nuclear Reactor Regulation
To:	Burkhardt L NIAGARA MOHAWK POWER CORP.
References
TASK-***, TASK-TM NUDOCS 8904240302
Download: ML17055E654 (36)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 April 14, 1989 Docket Nos. 50-220 and 50-410 M}. Lawrence Burkhardt III Executive Vice President, Nuclear Operations Niagara Mohawk Power Corporation 301 Plainfield Road

Syracuse, New York 13212

Dear Mr. Burkhardt:

The purpose of this letter is to request your prompt review and reporting of the status of implementation of TMI Action Plan Items at your facility.

As an enclosure we are providing a printout of all TMI items annotated where our tracking system indicates that implementation is not complete.

For the purpose of this request, implementation should be considered complete when, to the best of your knowledge, all actions necessary to satisfactorily meet the requirements of NNEG-0737 and NUREG-0737 Supplement 1 have been completed.

Where you have not fully completed an item as described

above, we request that you mark-up the enclosure to reflect your projected implementation date.

Add a short. note identifying remaining work (e.g.,

hardware, procedures,

training, technical specifications).

More explicit instructions are provided as part of the enclosure.

lie request that this information reach this office by April 18, 1989.

The information we are requesting will be utilized to validate our existing data base so that we can accurately respond to congressional inquiries concerning the status of implementation of TMI Action Plan Items.

In view of the importance of the information we request your personal attention and certification that the information is correct to the best of your knowledge.

This request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires December 31, 1989.

The estimated average burden hours is 40 person hours per owner response, including searching data sources, gathering and analyzing the data, and preparing the required letter.

Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Records 8904240302 S904l4 PDR ADOCK 05000220

S W

Hr. Lawrence Burkhar dt April 14, 1989 and Reports Management Branch, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission Washington, O.C.

20555; and to the Paperuark Reduction Project (3150-0011, Office of I<anagement and Budget, >iashington, O.C.

20503.

Your prompt attention to this matter within the requested time frame is appreciated.

Sincerely,

Enclosure:

As stated cc w/enclosure:

See next page ORIGINAL SIGNED BY Thomas E. Hurley, Director Office of Nuclear Reactor Regulation DISTRIBUTION NRC PDR Local PDR PDI-1 Rgg THurley JSniezek DPartlow SVarga BBoger CVogan RCapra MSlosson OGC EJor dan BGr imes ACRS (10)

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Document Name:

TMI ENCLOSURE Requestor's ID:

ARCHIVE Author's Name:

DUDLEY Document Comments:

encl. for TMI Action Plan Items letter

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GUIDELINES FOR UPDATING TMI STATUS 1.

The enclosure provides a complete listing of all TMI requirements from NUREG-0737 and NUREG-0737 Supplement 1.

Regulatory Guide 1.97 requirements, although addressed in Supplement I to NUREG-0737, are excluded since they did not originate from the TMI Action Plan.

This listing consists of a matrix of items applicable to both operating reactors and operating license applicants (NTOLS) as of November,

1980, as shown in NUREG-0737 Enclosure I and 2, respectively.

All items which are not listed identically in Enclosure I and 2 are marked with asterisks to indicate differences between operating reactor and NTOL requirements.

Whenever these differences occur, enter data in accordance with the appropriate title, regardless of the TMI Action Plan item number listed.

Your NRC Project Manager has indicated which issues are shown as unimplemented in the NRC tracking system.

Please review the entire listing for each licensed reactor unit.

Where an item was not applicable for your facility, mark N/A in the implementation status column.

2.

Where an item was applicable to your facility but no changes were necessary, mark NC in the implementation status column.

3.

Where an item was applicable to your facility and changes are complete mark C in the implementation status column.

If the date is readily available (month and year) we request you provide it, however, C is sufficient.

4.

Where an item was applicable to your facility and is not fully implemented, provide your projected implementation date (month and year) and a short note identifying the outstanding item (e.g.

hardware, procedures, training, technical specifications).

MULTI-P LANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I. A. 1. 1. 1

• I.A.l.l. 2 "I.A.1. 1. 3

• I.A.1. 1. 4 I.A.1.2 I.A.1.3. 1 I.A.1.3.2 I.A.2. 1. 1 I.A.2.1.2 I.A.2.1.3 I.A.2.1.4 I.A.2.1.5 I.A.2.3 I.A.3.1.1 I ~ A.3.1.2 I.A.3.1.3.A I.A.3. l. 3. B

• I.B.1.2 I.C.1.1 I.C. 1. 2. A I.C.1.2. B I. C. 1. 3. A I.C.1.3.B I.C.2 I.C.3 I.C.4 I.C.5 I.C.6

• I.C.7.1 AI.C. 7. 2

• I.C.8 I.D. 1 (See I.D.2.1 F001 F002 F002 F003 F004 F004 F005 F005 F006 F007 F008 & F071)

F009

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(PROC.

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(UPGRADED EOP'S)........................

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SHIFT TECHNICAL ADVISOR -

ON DUTY..

SHIFT TECHNICAL ADVISOR - TECH SPECS SHIFT TECHNICAL ADVISOR - TRAINED PER LL CAT B.

SHIFT TECHNICAL ADVISOR - DESCRIBE LONG TERM PROGRAM.

SHIFT SUPERVISOR RESPONSIBILITIES SHIFT MANNING LIMIT OVERTIMES SHIFT MANNING MIN SHIFT CREW.

IMMEDIATE UPGRADING OF RO 8( SRO TRAINING AND QUAL.

SRO EXPER.

IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. - SRO'S BE RO'S 1YR.

IMMEDIATE UPGRADING OF RO 8( SRO TRAINING AND QUAL.

3 MO. TRAINING.

IMMEDIATE UPGRADING OF RO 8c SRO TRAINING AND QUAL.

MODIFY TRAINING.

IMMEDIATE UPGRADING OF RO 8c SRO TRAINING AND QUAL.

FACILITY CERTIF ADMINISTRATION OF TRAINING PROGRAMS REVISE SCOPE 8( CRITERIA FOR LICENSING EXAHS -

INCREASE SCOPE REVISE SCOPE 8( CRITERIA FOR LICENSING EXAMS - INCREASE PASSING GRADE REVISE SCOPE 8 CRIT.

FOR LIC.

EXAMS - SIMULATOR PLANTS WITH SIMULATORS REVISE SCOPE 8 CRIT.

FOR LIC.

EXAMS SIMULATOR - OTHER PLANTS EVALUATION OF ORGANIZATION 8 MANAGEMENT SHORT-TERM ACCIDENT 8( PROCEDURES REVIEW -

SB LOCA.

SHORT-TERM ACCID.

8 PROCEDURES REV. - INADEQ.

CORE COOL.

REANAL. GUIDELINES.. ~

SHORT-TERM ACCIO.

8( PROCEDURES REV. - INADEQ.

CORE COOL.

REVISE PROCEDURES SHORT-TERM ACCID.

8 PROCEDURES REV TRANSIENTS 8( ACCOTS.

REANAL GUIDELINES SHORT-TERM ACCID.

8( PROCEDURES REV.

TRANSIENTS 8 ACCDRS.

REVISE PROCEDURES SHIFT 8( RELIEF TURNOVER PROCEDURES SHIFT-SUPERVISOR RESPONSIBILITY.

CONTROL-ROOM ACCESS FEEDBACK OF OPERATING EXPERIENCE VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES..

NSSS VENDOR REV.

OF PROC -

LOW POWER TEST PROGRAM.

NSSS VENDOR REV.

OF PROC POWER ASCENSION 8c EHER. PROCS..........

~...........

PILOT HON OF SELECTEO EMERGENCY PROC FOR NTOLS...................

~......-..-.-

CONTROL-ROOM DESIGN REVIEWS (ENTER DATA FOR HPA F008 8

HPA F-071).

PLANT-SAFETY PARAMETER DISPLAY CONSOLE - DESCRIPTION

MULTI-P LANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I.D.2.2 I. D.2.3

• I.G.1. 1

• I~ G. l. 2

• I.G.1. 3 II.B. 1. 1 II.B. 1. 2 II.B.1.3 II ~ B.2. 1

• II.B. 2. 2

• II. B. 2 ~ 3

• II. B.2. 4 "II. B. 3. 1

%II.B.3. 2

%II.B. 3. 3

• II. 8. 3. 4 II.B.4.1

• II. B.4. 2. A "II. 8.4. 2 ~ B II.D. 1. 1

• II. D. l. 2. A "II.D. 1. 2. B II.D. 1. 3

• II.D. 3. 1

• II.D.3. 2

• II. E. 1. 1. 1 (SEE NOTE 1)

• II.E. 1. l. 2 (SEE NOTE 2)

II. E. 1. 1. 3 (SEE NOTE 3)

F009 F009 F010 F010 F011 F012 F013 F013 F013 F014 F015 F015 F015 PLANT-SAFETY PARAMETER DISPLAY CONSOLE INSTALLED.

PLANT-SAFETY PARAMETER DISPLAY CONSOLE - FULLY IMPLEMENTED.

TRAINING DURING LOW-POWER TESTING " PROPOSE TESTS...

TRAINING DURING LOW-POWER TESTING - SUBMIT ANAL. 8 PROCS TRAINING DURING LOW-POWER TESTING - TRAINING L RESULTS REACTOR-COOLANT SYSTEM VENTS - DESIGN VENTS REACTOR-COOLANT SYSTEM VENTS - INSTALL VENTS (LL CAT B).

REACTOR-COOLANT SYSTEM VENTS -

PROCEDURES PLANT SHIELDING - REVIEW DESIGNS PLANT SHIELDING - CORRECTIVE ACTIONS TO ASSURE ACCESS........

PLANT SHIELDING PLANT MODIFICATIONS (LL CAT 8).

PLANT SHIELDING - EQUIPMENT QUALIFICATION-NOT TRACKED AS A TMI ACTION POSTACCIDENT SAMPLING - INTERIM SYSTEM..............................

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POSTACCIDENT SAMPLING - CORRECTIVE ACTIONS POSTACCIDENT SAMPLING -

PROCEDURES POSTACCIDENT SAMPLING -

PLANT MODIFICATIONS (LL CAT B).

TRAINING FOR MITIGATING CORE DAMAGE -

DEVELOP TRAINING PROGRAM.

TRAINING FOR. MITIGATING CORE DAMAGE - INITIAL TRAINING FOR MITIGATING CORE DAMAGE -

COMPLETE RELIEF 8 SAFETY VALVE TEST REQUIREMENTS - SUBMIT PROGRAM.

RELIEF 8 SAFETY VALVE TEST REQUIREMENTS -

COMPLETE TESTING.

RELIEF L SAFETY VALVE TEST REQUIREMENTS - PLANT SPECIFIC REPORT RELIEF 8 SAFETY VAVLE TEST REQUIREMENTS - BLOCK-VALVE TESTING.

VALVE POSITION INDICATION - INSTALL DIRECT INDICATIONS OF VALVE POS VALVE POSTION INDICATION - TECH SPECS.................................

AFS EVALUATION-ANALYSIS AFS EVALUATION-SHORT TERM NODS

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NOTE 1 THE ITEM LISTED IS FROM NUREG-0737, ENCLOSURE 2 AND IS APPLICABLE TO NTOLS'S ONLY NOTE 2 - THE ITEM LISTED IS FOR ALL PLANTS (OPERATING REACTORS AND NTOL'S)

NOTE 3 - THE ITEM LISTED,'IS FOR ALL PLANTS (OPERATING REACTORS AND NTOL'S) 4 ~

'I

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS II.E.1.2.1.A II. E. 1.2. 1. B II.E.1.2.2.A

• II. E. l. 2. 2. B

• II. E. l. 2. 2. C

• II.E.3. 1. 1

• II. E. 3.1. 2 II.E.4.1.1

• II.E.4.1.2

• II. E.4. 1. 3 II. E.4. 2. 1-4 "II.E.4.2.5.A

%II.E.4.2.5.B II.E.4.2.6 II.E.4.2.7

• II. E.4.2. 8

• II.F.l. 1

• II. F. 1. 2. A "II. F. 1. 2. B "II. F. l. 2. C

• II.F. 1. 2. D "II.F. l. 2. E "II. F. 1. 2. F AII. F. 2. 1 "II.F. 2. 2 "II.F.2.3

• II.F. 2.4 "II.G.l.l

• II.G.1. 2 II.K. 1 (Oper.

F016 F017 F018 F019 F019 F020 F020 F021 F022 F023 f024 F025 F026 F026 Reactors Only)

AFS INITIATION 8( FLOW-CONTROL GRADE AFS INITIATION 8( FLOW SAFETY GRADE AFS INITIATION5 FLOW -

FLOW INDICATION CONTROL GRADE AFS INITIATION 84 FLOW - LL CAT A TECH SPECS AFS INITIATION5 FLOW - SAFETY GRADE EMERGENCY POWER FOR PRESSURIZER HEATERS -

UPGRADE POWER SUPPLY..

EMERGENCY POWER FOR PRESSURIZER HEATERS TECH SPECS DEDICATED HYDROGEN PENETRATIONS DESIGN.

DEDICATED HYDROGEN PENETRATIONS REVIEW 8 REVISE H2 CONTROL PROC.

DEDICATED HYDROGEN PENETRATION - INSTALL

-CONTAINMENT ISOLATION DEPENDABILITY - IMP.

DIVERSE ISOLATION.

CONTAINMENT ISOLAT. DEPENDABILITY CNTMT PRESS.

SETPT.

SEECIFIY PRESS CONTAINMENT ISOLATION DEPENDABILITY -

CNTMT PRESSURE SETPT.

MOOS CONTAINMENT ISOLATION DEPENDABILITY -

CNTMT PURGE VALVES CONTAINMENT ISOLATION DEPENDABILITY - RADIATION SIGNAL ON PURGE VALVES.

CONTAINMENT ISOLATION DEPENDABLITY - TECH SPECS ACCIDENT MONITORING PROCEDURES ACCIDENT MONITORING - NOBLE GAS MONITOR..

ACCIDENT MONITORING - IODINE/PARTICULATE SAMPLING.

ACCIDENT - MONITORING - CONTAINMENT HIGH-RANGE MONITOR..

ACCIDENT - MONITORING - CONTAINMENT PRESSURE ACCIDENT - MONITORING - CONTAINMENT WATER LEVEL ACCIDENT MONITORING - CONTAINMENT HYDROGEN.

INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE COOLING -

PROCEDURES INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE COOLING -

SUBCOOL METER.

INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE COOLING - DESC.

OTHER.

INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE CLING INSTLL ADD'L INSTRUMENTATION.

POWER SUPP.

FOR PRESSURIZER

RELIEF, BLOCK VALVES 8c LEVEL IND.

UPGRADE POWER SUPP.

FOR PRESSURIZER

RELIEF, BLOCK VALVES 8( LEVEL IND. - TECH SP IE BULLETINS 05, 79-06, 79-08.

ISSUE NUMBER MULTI-PLANT ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS 0

~

"II.K.l.5

• II.K.1.10

'I I. K.l. 20

• II. K. 1: 21

• II. K.l. 22

• II. K. 1. 23

• II. K. 2. 2

%II. K.2.8 II.K.2.9 II.K.2.10

• II. K. 2. 11 II.K.2.13 II.K. 2. 14 II. K.2. 15 II.K.2.16 II. K.2. 17 II. K.2. 19 "II.K.2. 20 "II.K. 3. 1. A "II.K.3. 1. B II.K.3.2 II.K.3. 3 II.K.3. 5. A II. K. 3.5. B II.K. 3. 7 II.K. 3. 9 II. K. 3. 10 II. K.3. 11 II.K.3. 12. A II. K. 3. 12. B II. K. 3. 13. A II. K.3. 13. B F027 F028 F029 F030 F031 F032 F033 F035 F036 F037 F038 F039 F039 F040 F041 F042 F043 F043 IE BULLETINS - REVIEW ESF VALVES IE BULLETINS - OPERABILITY STATUS IE BULLETINS -

PROMPT MANUAL REACTOR TRIP.

IE BULLETINS AUTO SG ANTICIPATORY REACTOR TRIP....

IE BULLETINS - AUX. HEAT REM SYSTEM, PROC.

IE BULLETINS RV LEVEL, PROCEDURES ORDERS ON B8W PLANTS PROCEDURES TO CONTROL AFW IND OF ICS ORDERS ON B&W PLANTS -

UPGRADE AFW SYSTEM.

ORDERS ON B&W PLANTS -

FEMA ON ICS ORDERS ON B8W PLANTS - SAFETY-GRADE TRIP.

ORDERS ON B8W PLANTS OPERATOR TRAINING.

ORDERS ON B8W PLANTS - THERMAL MECHANICAL REPORT (CE & W PLANTS ALSO).

ORDERS ON B8W PLANTS - LIFT FREQUENCY OF PORV'S 8 SV's......

ORDERS ON B8W PLANTS - EFFECTS OF SLUG FLOW.......................

ORDERS ON B8W PLANTS RCP SEAL DAMAGE ORDERS ON B&W PLANTS - VOIDING IN RCS (CE 8

W PLANTS ALSO).

BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCE THROUGH STM GENERATOR.

ORDERS ON B&W PLANTS - SYSTEM RESPONSE TO SB LOCA.

B&0 TASK FORCE AUTOMATIC PORV ISOLATION DESIGN.

FINAL RECOMMENDATIONS, B80 TASK FORCE AUTO PORV ISO TEST/INSTALL B80 TASK FORCE -

REPORT ON PORV FAILURES B80 TASK FORCE -

REPORTING SV & RV FAILURES AND CHALLENGES B&0 TASK FORCE - AUTO TRIP OF RCP'S PROPOSED MODIFICATIONS.

B&0 TASK FORCE - AUTO TRIP OF RCP'S MODIFICATIONS.......................

B80 TASK FORCE - EVALUATION OF PORV OPENING PROBABILITIES B80 TASK FORCE - PID CONTROLLER MODIFICATION.

B8(0 TASK FORCE PROPOSED ANTICIPATORY TRIP MODIFICATIONS.

B80 TASK FORCE - JUSTIFY USE OF CERTAIN PORV.

B80 TASK FORCE ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED MODS B80 TASK FORCE ANTICIPATORY TRIP ON TURBINE TRIP INSTALL MODS B80 TASK FORCE HPCI 8

RCIC SYSTEM INITIATION LEVELS ANALYSIS...

~.-..

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B80 TASK FORCE HPCI 8

RCIC INITIATION LEVELS MODIFICATION..

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ISSUE NUMBER MULTI-PLANT ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS II. K. 3. 16. B II. K.3. 17 II. K. 3. 18. A II. K. 3. 18. B II.K.3. 18. C

• II. K.3. 19

• II. K. 3. 20 II. K. 3. 21. A II. K. 3. 21. B II. K.3. 22. A II.K.3. 22. B II.K.3. 24 II. K.3. 25. A II.K.3. 25. B II. K.3. 27 II. K. 3. 28

• II. K. 3. 29 II.K.3. 30. A II.K.3. 30. B II. K.3. 30. C II. K.3. 31

• II.K.3.40 "II. K. 3. 43 II.K.3.44 II.K. 3.45 II.K.3.46

• II.K.3. 57 III.A.1.1, F046 F047 F048 F048 F048 F049 F050 F050 F051 F051 F052 F053 F054 F055 F056 F057 F058 F059 F060 F061 F062

• II. K.3. 14 F044 II. K. 3. 15 F045 II. K.3. 16A F046 B80 TASK B&0 TASK B80 TASK B80 TASK B80 TASK B80 TASK B80 TASK B&0 TASK B80 TASK B80 TASK B&0 TASK B&0 TASK B&0 TASK B80 TASK B&0 TASK B&0 TASK B80 TASK B&0 TASK B&0 TASK B80 TASK B&0 TASK B80 TASK B80 TASK B80 TASK B80 TASK B80 TASK B80 TASK B80 TASK

RESPONSE

IDENTIFY EMERGENC FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE

%'ORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE FORCE TO LIS WATER Y PREPA

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- ISO CONDENSER ISOLATION ON HIGH RAD.

- MODIFY HPCI & RCIC BRK DETECTION CIRCUITRY

- CHALLENGE 8 FAILURE OF RELIEF VALVES STUDY..........

CHALLENGE & FAILURE OF RELIEF VALVES MODIFICATIONS.

ECC SYSTEM OUTAGES..

- ADS ACTUATION STUDY.

- ADS ACTUATION PROPOSED MODIFICATIONS ADS ACTUATION MODIFICATIONS-

- INTERLOCK RECIRCULATORY PUMP MODIFICATIONS..

LOSS OF SVC WATER AT BRP RESTART OF CSS & LPCI LOGIC DESIGN.

RESTART OF CSS

& LPCI. LOGIC DESIGN MODIFICATIONS

- RCIC SUCTION VERIFICATION PROCEDURES

- RCIC SUCTION MODIFICATION.

- SPACE COOLING FOR HPCIlRCI LOSS OF AC POWER.

POWER ON PUMP SEALS PROPOSED MODIFICATIONS.

POWER ON PUMP SEALS MODIFICATIONS COMMON REFERENCE LEVEL FOR BWRS..

- QUALIFICATION OF ADS ACCUMULATORS PERFORMANCE OF ISOLATION CONDENSERS SCHEDULE FOR OUTLINE OF SB LOCA MODEL SB LOCA MODEL, JUSTIFICATION.

- SB LOCA METHODS NEW ANALYSES COMPLIANCE WITH CFR 50.46..

RCP SEAL DAMAGE -

COVERED BY II.K.2. 16 AND II.K. 3. 25

- EFFECTS OF SLUG FLOW COVERED BY II.K. 2. 15.

- EVALUATE TRANSIENT WITH SINGLE FAILURE ANALYSES TO SUPPORT.

T OF CONCERNS FROM ACRS CONSULTANT.

SOURCES PRIOR TO MANUAL ACTIVATION OF ADS

REDNESS, SHORT'ERM.

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS III.A.1.2. 1 III.A.1.2. 2 (SEE F063,

F064, F065)

III.A.1. 2. 3 (SEE F063,

F064, F065)

III.A.2.1 F067 III.A.2.2 F068

• III.D.l.l. 1

• III.D.l.l. 2 III.D. 3. 3. 1 III.D.3.3.2

=

F069 III.D.3.4. 1 F070

• III.D. 3.4. 2 F070

• III.D.3.4.3 MPA-F008 F008 MPA-F063 F063 MPA-F064 F064 MPA-F065 F065 MPA-F071 F071 MPA-B072 8072 MPA-8083 B083 67.4.1 G001 UPGRADE EMERGENCY SUPPORT FACILITIES - INTERIM TSC OSC 8

EOF UPGRADE EMERGENCY SUPPORT FACILITIES-DESIGN-INCORP.

INTO F063/F064/f065.

(

UPGRADE EMER SUPPORT FACILITIES -

MODS INCORPOR.

INTO F063, F064 8( F065.

UPGRADE PREPAREDNESS -

UPGRADE EMERGENCY PLANS TO APP.

E.

10 CFR 50..

UPGRADE PREPAREDNESS METEOROLOGICAL DATA.

PRIMARY COOLANT OUTSIDE CONTAINMENT -

LEAK REDUCTION.

PRIMARY COOLANT OUTSIDE CONTAINMENT - TECH SPECS INPLANT RAD. MONIT. - PROVIDE MEANS TO DETER.

PRESENCE OF= RADIOIODINE..

INPLANT RADIATION MONIT. - MODIFICATIONS TO ACCURATELY MEAS.

IODINE CONTROL ROOM HABITABILITY REVIEW..

CONTROL ROOM HABITABILITY SCHEDULE MODIFICATIONS CONTROL ROOM HABITABILITY IMPLEMENT MODIFICATIONS I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN.

III.A.1.2 TECHNICAL SUPPORT CENTER III.A.1.2 OPERATIONAL SUPPORT CENTER..

III.A.1. 2 EMERGENCY OPERATIONS FACILITY.

I.D.1.2 DETAILED CONTROL ROOM REVIEW (FOLLOWUP TO F-8).......

NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16 8( 83-02)

TECH SPEC COVERED BY GENERIC LETTERS 83-26 8( 83-37 FOR NUREG-0737.

REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12).

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+~7~ APc&fx%4........

Document Name:

TMI ENCLOSURE Requestor's ID:

ARCHIVE Author's Name:

DUDLEY Document Comments:

encl. for TMI Action Plan Items letter

GUIDELINES FOR UPDATING THI STATUS 1.

The enclosure provides a complete listing of all TMI requirements from NUREG-0737,and NUREG-0737 Supplement 1.

Regulatory Guide 1.97 requirements, although addressed fn Supplement 1 to NUREG-0737, are excluded since they did not originate from the TMI Action Plan.

This listing consists of a matrix of items applicable to both operating reactors and operating license applicants (NTOLS) as of November,

1980, as shown in NUREG-0737 Enclosure 1 and 2, respectively.

All items which are not listed identically fn Enclosure 1 and 2 are marked with asterisks to indicate differences between operating reactor and NTOL requirements.

Whenever these differences occur, enter data in accordance with the appropriate title, regardless of the TMI Action Plan item number listed.

Your NRC Project Manager has indicated which issues are shown as unimplemented in the NRC tracking system.

Please review the entire listing for each licensed reactor unit.

Where an item was not applicable for your facility, mark N/A in the implementation status column.

2.

Where an item was applicable to your facility but no changes were necessary, mark NC in the implementation status column.

3.

Where. an item was applfcable'to your facility and changes are complete mark C in the implementation status column.

If the date is readily available (month and year) we request you provide it, however, C is sufficient.

4.

Where an item was applicable to your facility and fs not fully implemented, provide your projected implementation date (month and year) and a short note identifying the outstanding item (e.g.

hardware, procedures, training, technical specifications).

A

MULTI"PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I.A.1.1.1 "I.A.1. 1. 2

• I.A.1. 1. 3

• I.A.l.l. 4 I.A.1.2 I.A.1.3.1 I.A.1.3.2 I.A.2.1.1 I.A.2.1.2 I.A.2.1.3 I.A.2.1.4 I.A.2. 1. 5 I.A.2. 3 I.A.3.1.1 I.A.3.1.2 I.A.3.1.3.A I.A.3. 1. 3. B AI.B.1.2 I.C.1.1 I. C.1.2.A I. C.1.2. B I.C.1.3.A I. C. 1. 3. B I.C.2 I.C.3 I. C.4 I.C.5 I.C.G "I.C.7.1 AI.C. 7. 2

• I.C.8 I.D. 1 (See I.D.2.1 F001 F002 F002 F003 F004 F004 F005 F005 F006 F007 F008 8( F071)

F009

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GEN.

PKG. )

RADED EOP'S)

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..... 4~ 7.. MHPNMMi.'~o... ~.

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SHIFT TECHNICAL ADVISOR -

ON DUTY; SHIFT TECHNICAL ADVISOR TECH SPECS SHIFT TECHNICAL ADVISOR TRAINED PER LL CAT B.

SHIFT TECHNICAL ADVISOR - DESCRIBE LONG TERM PROGRAM.

SHIFT SUPERVISOR RESPONSIBILITIES SHIFT MANNING LIMIT OVERTIMES SHIFT MANNING MIN SHIFT CREW.

IMMEDIATE UPGRADING OF RO 8( SRO TRAINING AND EQUAL. -

SRO EXPER.

IMMEDIATE UPGRADING OF RO 8c SRO TRAINING AND EQUAL. - SRO'S BE RO'S 1YR..

IMMEDIATE UPGRADING OF RO 8c SRO TRAINING AND gUAL. - 3 MO. TRAINING.

IMMEDIATE UPGRADING OF RO 8c SRO TRAINING AND QUAL.

MODIFY TRAINING.

IMMEDIATE UPGRADING OF RO 8( SRO TRAINING AND OVAL. FACILITY CERTIF.

ADMINISTRATION OF TRAINING PROGRAMS REVISE SCOPE 8c CRITERIA FOR LICENSING EXAMS INCREASE SCOPE REVISE SCOPE 8( CRITERIA FOR LICENSING EXAMS -

INCREASE PASSING GRADE REVISE SCOPE 8( CRIT.

FOR LIC.

EXAMS SIMULATOR PLANTS WITH SIMULATORS REVISE SCOPE 8( CRIT.

FOR LIC.-EXAMS SIMULATOR - OTHER PLANTS..........

EVALUATION OF ORGANIZATION 8( MANAGEMENT..

SHORT-TERM ACCIDENT 8 PROCEDURES REVIEW -

SB LOCA.

SHORT-TERM ACCID.

8( PROCEDURES REV. -

INADEQ.

CORE COOL.

REANAL. GUIDELINES SHORT-TERM ACCID.

8 PROCEDURES REV. - INADEQ.

CORE COOL.

REVISE PROCEDURES SHORT-TERM ACCID.

8( PROCEDURES REV TRANSIENTS 8( ACCDTS.

REANAL GUIDELINES (PROC SHORT-TERM ACCID.

8( PROCEDURES REV.

TRANSIENTS 8 ACCDRS.

REVISE PROCEDURES (UPG SHIFT 8( RELIEF TURNOVER PROCEDURES SHIFT-SUPERVISOR RESPONSIBILITY.

CONTROL-ROOM ACCESS FEEDBACK OF OPERATING EXPERIENCE

'VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES NSSS VENDOR REV.

OF PROC -

LOW POWER TEST PROGRAM.

NSSS VENDOR REV.

OF PROC -

POWER ASCENSION 8c EMER.

PROCS PILOT MON OF SELECTED EMERGENCY PROC FOR NTOLS

( CONTROL-ROOM DESIGN REVIEWS (ENTER DATA FOR MPA.F008 8

MPA F-071).

1 PLANT-SAFETY PARAMETER DISPLAY CONSOLE - DESCRIPTION.

P MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I.D.2.2 I.D.2.3

• I.G.1. 1

• I.G.l. 2

• I.G.1. 3 II.B.1. 1 II.8.1.2 II.B. 1. 3 II.B.2.1

• II.B.2. 2 "II.B. 2. 3

• II.B.2. 4 "II. 8.3. 1 AII. 8.3. 2 AII. B. 3. 3 XII.8.3.4 II.B.4.1 XII.B.4.2.A

• II.B.4.2.8 II.D.1.1

• II.D.1.2. A

• II.D.1.2. 8 II.D.1.3

• II. D.3. 1 "II. D.3. 2 "II.E.l.l. 1 (SEE NOTE 1)

"II.E. 1. 1. 2 (SEE NOTE 2)

II.E.1.1.3 (SEE NOTE 3)

F009 F009 F010 F010 F011 F012 F013 F013-F013 F014 F015 F015 F015 PLANT-SAFETY PARAMETER DISPLAY CONSOLE INSTALLED.

PLANT-SAFETY PARAMETER DISPLAY CONSOLE - FULLY IMPLEMENTED.

TRAINING DURING LOW-POWER TESTING -

PROPOSE TESTS.........

TRAINING DURING LOW-POWER TESTING - SUBMIT ANAL.

8c PROCS TRAINING DURING LOW-POWER TESTING TRAINING 8c RESULTS REACTOR-COOLANT SYSTEM VENTS - DESIGN VENTS...........

~ ~...

REACTOR-COOLANT SYSTEM VENTS INSTALL VENTS (LL CAT 8)..

REACTOR-COOLANT SYSTEM VENTS -

PROCEDURES PLANT SHIELDING - REVIEW DESIGNS.

PLANT SHIELDING - CORRECTIVE ACTIONS TO ASSURE ACCESS......

PLANT SHIELDING - PLANT MODIFICATIONS (LL CAT 8)

PLANT SHIELDING - E(UIPMENT QUALIFICATION-NOT TRACKED AS A TMI POSTACC IDENT SAMPLING INTERIM SYSTEM.

POSTACCIDENT SAMPLING - CORRECTIVE ACTIONS.

POSTACCIDENT SAMPLING -

PROCEDURES POSTACCIDENT SAMPLING -

PLANT MODIFICATIONS (LL CAT 8).

TRAINING FOR MITIGATING CORE DAMAGE - DEVELOP TRAINING PROGRAM.

TRAINING FOR MITIGATING CORE DAMAGE - INITIAL TRAINING FOR MITIGATING CORE DAMAGE - COMPLETE RELIEF 8( SAFETY VALVE TEST REQUIREMENTS SUBMIT PROGRAM.

RELIEF 8( SAFETY VALVE TEST RE(UIREMENTS -

COMPLETE TESTING.

RELIEF L SAFETY VALVE TEST REQUIREMENTS - PLANT SPECIFIC REPORT RELIEF 8( SAFETY VAVLE TEST RE(UIREMENTS - BLOCK-VALVE TESTING..

VALVE POSITION INDICATION - INSTALL DIRECT INDICATIONS OF VALVE VALVE POSTION INDICATION - TECH SPECS AFS EVALUATION-ANALYSIS........................................

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ACTION ITEM.... ~ - ~--

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POS AFS EVALUATION-SHORT TERM MODS AFS -LONG TERM MODS

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NOTE 1 - THE ITEM LISTED IS FROM NUREG-0737, ENCLOSURE 2 AND IS APPLICABLE TO NTOLS'S ONLY NOTE 2 - THE ITEM LISTED IS FOR ALL PLANTS (OPERATING REACTORS AND NTOL'S)

NOTE 3 - THE ITEM LISTED IS FOR ALL PLANTS (OPERATING REACTORS AND NTOL'S) 1p kf I

I

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS II.E.1.2.1.A II.E.1.2.1.B II.E.1.2.2.A

• II.E. 1.2. 2. B

• II.E. 1.2. 2. C

• II.E.3.1. 1 "II.E. 3. 1. 2 II.E.4.1.1

• II. E.4. 1. 2

• II.E.4.1.3 II. E.4. 2. 1-4

• II.E.4.2. 5. A

• II. E.4.2.5. 8 II. E.4. 2. 6 II. E.4.2. 7

• II. E.4. 2. 8 "II.F. 1. 1

• II.F.1.2.A

%II.F.1.2.B

• II.F.1.2.C

• II. F. 1.2. D

• II.F.1.2.E

• II. F. 1.2. F

%II.F.2. 1 "II.F.2.2-

• II. F. 2. 3

• II.F. 2.4

%II.G.1.1 "II.G.1. 2 II.K.1 (Oper.

F016 F017 F018 F019 F019 F020 F020 F021 F022 F023 F024 F025 F026 F026 Reactors Only)

AFS INITIATION 8( FLOW-CONTROL GRADE AFS INITIATIONL FLOW SAFETY GRADE AFS INITIATION8 FLOW FLOW INDICATION CONTROL GRADE AFS INITIATION Ec FLOW LL CAT A TECH SPECS AFS INITIATION 8c FLOW SAFETY GRADE EMERGENCY POWER FOR PRESSURIZER HEATERS UPGRADE POWER SUPPLY.

EMERGENCY POWER FOR PRESSURIZER HEATERS TECH SPECS DEDICATED HYDROGEN PENETRATIONS DESIGN.

DEDICATED HYDROGEN PENETRATIONS - REVIEW 8( REVISE H2 CONTROL PROC...........

DEDICATED HYDROGEN PENETRATION INSTALL.

CONTAINMENT ISOLATION DEPENDABILITY IMP.

DIVERSE ISOLATION.

CONTAINMENT ISOLAT. DEPENDABILITY -

CNTMT PRESS.

SETPT.

SEECIFIY PRESS CONTAINMENT ISOLATION DEPENDABILITY CNTMT PRESSURE SETPT.

MODS CONTAINMENT ISOLATION DEPENDABILITY CNTMT PURGE VALVES CONTAINMENT ISOLATION DEPENDABILITY - RADIATION SIGNAL ON PURGE VALVES CONTAINMENT ISOLATION DEPENDABLITY - TECH SPECS ACCIDENT - MONITORING -

PROCEDURES ACCIDENT - MONITORING NOBLE GAS MONITOR.

ACCIDENT - MONITORING IODINE/PARTICULATE SAMPLING ACCIDENT - MONITORING - CONTAINMENT HIGH-RANGE MONITOR.

ACCIDENT - MONITORING -

CONTAINMENT PRESSURE ACCIDENT - MONITORING -

CONTAINMENT WATER LEVEL.

ACCIDENT - MONITORING CONTAINMENT HYDROGEN.

INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE COOLING PROCEDURES INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE COOLING -

SUBCOOL METER.

INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE COOLING DESC.

OTHER.

INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE CLING INSTLL ADD'L INSTRUMENTAT EMPOWER SUPP.

FOR PRESSURIZER

RELIEF, BLOCK VALVES Ec LEVEL IND. -

UPGRADE.

'POWER SUPP.

FOR PRESSURIZER

RELIEF, BLOCK VALVES 8 LEVEL IND. - TECH SP

'. IE BULLETINS 05, 79-06, 79-08 ION.

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P MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE Oo E

LICENSEE IMPLEMENTATION STATUS

• II. K. 1. 5 "II. K.l. 10

• II. K.l. 20

• II. K.l. 21

• II. K.l. 22

• II. K. 1. 23

• II. K.2. 2

%II. K. 2.8 II.K. 2. 9 II. K. 2. 10

• II. K. 2. 11 II.K.2.13 II. K. 2. 14 II. K. 2. 15 II.K.2. 16 II.K.2. 17 II. K.2. 19

• II. K. 2. 20

• II.K.3.1.A AII. K. 3. 1. B II.K.3.2 II.K.3.3 II.K.3.5.A II.K.3.5.B II.K.3.7 II.K. 3. 9 II.K.3.10 II. K. 3. 11 II. K. 3. 12. A II. K.3. 12. B II. K. 3. 13. A II. K. 3. 13. B F027 F028 F029 F030 F031 F032 F033 f035 F036 F037 F038 F039 F039 F040 F041 F042 F043 F043 IE BULLETINS -

REVIEW ESF VALVES IE BULLETINS - OPERABILITY STATUS IE BULLETINS -

PROMPT MANUAL REACTOR TRIP.

IE BULLETINS AUTO SG ANTICIPATORY REACTOR TRIP..

IE BULLETINS - AUX. HEAT REM SYSTEM, PROC-......... -..........

IE BULLETINS -

RV LEVEL, PROCEDURES ORDERS ON B8W PLANTS PROCEDURES TO CONTROL AFW IND OF ICS ORDERS ON B8W PLANTS UPGRADE AFW SYSTEM-ORDERS ON B8(W PLANTS -

FEMA ON ICS ORDERS ON B8W PLANTS - SAFETY-GRADE TRIP ORDERS ON B8(W PLANTS - OPERATOR TRAINING ORDERS ON B8(W PLANTS - THERMAL MECHANICAL REPORT (CE 8(

W PLANTS ALSO ORDERS ON B8W PLANTS - LIFT FREQUENCY OF PORV'S 8 SV's ORDERS ON B8(W PLANTS. EFFECTS OF SLUG FLOW.

ORDERS ON B8W PLANTS ;

RCP SEAL DAMAGE ORDERS-ON B8W PLANTS - VOIDING IN RCS (CE 8(

W PLANTS ALSO).

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~ BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCE THROUGH STM GENERA ORDERS ON B8(W PLANTS - SYSTEM RESPONSE TO SB LOCA.

B80 TASK FORCE - AUTOMATIC PORV ISOLATION DESIGN.

FINAL RECOMMENDATIONS, B80 TASK FORCE - AUTO PORV ISO TEST/INSTALL.

B80 TASK FORCE -

REPORT ON PORV FAILURES............................

B80 TASK FORCE - REPORTING SV 8( RV FAILURES AND CHALLENGES B80 TASK FORCE AUTO TRIP OF RCP'S PROPOSED MODIFICATIONS B80 TASK FORCE AUTO TRIP OF RCP'S MODIFICATIONS B80 TASK FORCE EVALUATION OF PORV OPENING. PROBABILITIES..

B80 TASK FORCE - PID CONTROLLER MODIFICATION B80 TASK FORCE PROPOSED ANTICIPATORY TRIP MODIFICATIONS..

B80 TASK FORCE - JUSTIFY USE OF CERTAIN PORV.

B8(0 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED MODS B80 TASK FORCE ANTICIPATORY TRIP ON TURBINE TRIP INSTALL MODS B80 TASK FORCE HPCI 8( RCIC SYSTEM INITIATION LEVELS ANALYSIS.....

'B80 TASK FORCE - HPCI 8( RCIC INITIATION LEVELS MODIFICATION.

~i II f

ISSUE NUMBER MULTI-PLANT ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

• II.K.3.14 II. K.3. 15 II. K.3. 16A II. K. 3. 16. B II. K.3. 17 II.K. 3. 18. A II.K. 3. 18. B II. K. 3,18. C

• II. K. 3. 19

• II. K. 3. 20 II.K. 3. 21. A II.K.3. 21. B II. K. 3. 22. A II. K. 3. 22. B II. K. 3. 24 II.K. 3. 25. A II.K.3.25.B II. K. 3. 27 II.K. 3. 28 XII.K.3.29 II. K.3. 30. A II.K.3 ~ 30. B II. K. 3. 30. C II. K.3. 31 XII.K.3.40 "II.K. 3. 43 II. K.3. 44 II ~ K. 3. 45 II'.3.46 "II. K. 3. 57 III.A.1. 1 F044 F045 F046 F046 F047 F048 F048 F048 F049 F050 F050 F051 F051 F052 F053 F054 F055 F056 F057 F058 F059 F060 F061 F062 880 TASK FORCE - ISO CONDENSER ISOLATION ON HIGH RAD.

B&0 TASK FORCE - MODIFY HPCI 8 RCIC BRK DETECTION CIRCUITRY.

B&0 TASK FORCE CHALLENGE & FAILURE OF RELIEF VALVES STUDY.

B&0 TASK FORCE CHALLENGE & FAILURE OF RELIEF VALVES MODIFICATIONS B80 TASK FORCE ECC SYSTEM OUTAGES B80 TASK FORCE - ADS ACTUATION STUDY B80 TASK FORCE ADS ACTUATION PROPOSED MODIFICATIONS.

B80 TASK FORCE - ADS ACTUATION MODIFICATIONS B&0 TASK FORCE INTERLOCK RECIRCULATORY PUMP MODIFICATIONS B80 TASK FORCE LOSS OF SVC WATER AT BRP B80 TASK FORCE RESTART OF CSS

& LPCI LOGIC DESIGN.

B8(0 TASK FORCE RESTART OF CSS 8

LPCI LOGIC DESIGN MODIFICATIONS B&0 TASK FORCE - RCIC SUCTION VERIFICATION PROCEDURES B80 TASK FORCE RCIC SUCTION MODIFICATION.

B8(0 TASK FORCE -

SPACE COOLING FOR HPCI/RCI LOSS OF AC POWER B80 TASK FORCE -

POWER ON PUMP SEALS PROPOSED MODIFICATIONS.. - -.....

B80 TASK FORCE -

POWER ON PUMP SEALS MODIFICATIONS B8(0 TASK FORCE -

COMMON REFERENCE LEVEL FOR BWRS B80 TASK FORCE QUALIFICATION OF ADS ACCUMULATORS B80 TASK FORCE -

PERFORMANCE OF ISOLATION CONDENSERS B&0 TASK FORCE SCHEDULE FOR OUTLINE OF SB LOCA MODEL B&0 TASK FORCE -

SB LOCA MODEL, JUSTIFICATION.

B&0 TASK FORCE SB LOCA METHODS NEW ANALYSES B80 TASK FORCE COMPLIANCE WITH CFR 50.46.

B&0 TASK FORCE RCP SEAL DAMAGE COVERED BY II.K. 2. 16 AND II.K. 3.25..

B&0 TASK FORCE EFFECTS OF SLUG FLOW -

COVERED BY II K 2 15...........

B80 TASK FORCE EVALUATE TRANSIENT WITH SINGLE FAILURE B80 TASK FORCE - ANALYSES TO SUPPORT

RESPONSE

TO LIST OF CONCERNS FROM ACRS CONSULTANT IDENTIFY WATER SOURCES PRIOR TO MANUAL ACTIVATION OF ADS..

EMERGENCY PREPAREDNESS, SHORT TERM.

C la 1f

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS III.A.1. 2. 1 III.A.1. 2. 2 (SEE f063, III.A.1. 2. 3 (SEE F063, III.A.2. 1 III.A.2. 2

• III.D.l.l. 1 "III.D.1.1. 2 III.D. 3 ~ 3. 1 III.D.3.3.2 III.D. 3.4. 1 "III. D. 3.4. 2 "III. D. 3.4. 3 MPA-F008 HPA-F063

'PA-F064 HPA-F065 MPA-F071 HPA-B072 HPA-B083 67.4. 1

F064, F065)

F064, F065)

F067 F068 F069 F070 F070 F008 F063 F064 F065 F071 B072 B083 G001 UPGRADE EMERGENCY SUPPORT FACILITIES - INTERIM TSC OSC L EOF UPGRADE EMERGENCY SUPPORT FACILITIES"DESIGN-INCORP. INTO F063/F064/F065.

UPGRADE EMER SUPPORT FACILITIES " MOOS INCORPOR.

INTO F063, F064 84 F065.

UPGRADE PREPAREDNESS UPGRADE EMERGENCY PLANS TO APP.

E.

10 CFR 50.

UPGRADE PREPAREDNESS - METEOROLOGICAL DATA.

PRIMARY COOLANT OUTSIDE CONTAINMENT -

LEAK REDUCTION.

PRIMARY COOLANT OUTSIDE CONTAINMENT " TECH SPECS INPLANT RAD. HONIT.

PROVIDE MEANS TO DETER.

PRESENCE Of RADIOIODINE INPLANT RADIATION MONIT. - HODIfICATIONS TO ACCURATELY HEAS.

IODINE CONTROL ROOM MABITABILITY REVIEW.

CONTROL ROOM HABITABILITY-SCHEDULE MODIFICATIONS CONTROL ROOM HABITABILITY-IMPLEMENT MODIFICATIONS..

I.D.l.l DETAILED CONTROL ROOM DESIGN REVIEM PROGRAM PLAN.

III.A.1.2 TECHNICAL SUPPORT CENTER.

III.A.1.2 OPERATIONAL SUPPORT CENTER III.A.1. 2 EMERGENCY OPERATIONS FACILITY.

I.D.1.2 DETAILED CONTROL ROOH REVIEM (FOLLOMUP TO F-8)

NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16 8( 83"02).

TECH SPEC COVERED BY GENERIC LETTERS 83-26 8( 83-37 FOR NUREG-0737 REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-'12)

QD7 ~~g g,~M~PP~

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